Joint DIII-D/EAST research on the development of a high poloidal beta scenario for the steady state missions of ITER and CFETR
Journal Article
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· Plasma Physics and Controlled Fusion
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- General Atomics, San Diego, CA (United States)
- Chinese Academy of Sciences (CAS), Hefei (China). Inst. of Plasma Physics
- Oak Ridge Associated Univ., Oak Ridge, TN (United States)
- Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
- Columbia Univ., New York, NY (United States)
- Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
- Huazhong Univ. of Science and Technology, Wuhan (China)
- Commissariat a l'Energie Atomique et aux Energies Alternatives (CEA), Saint-Paul-Les-Durance (France)
- Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States). Plasma Science and Fusion Center
- Univ. of California, Los Angeles, CA (United States). Dept. of Physics and Astronomy
Experimental and modeling investigations on the DIII-D and EAST tokamaks show the attractive transport and stability properties of fully noninductive, high poloidal-beta (βP) plasmas, and their suitability for steady-state operating scenarios in ITER and CFETR. A key feature of the high-βP regime is the large-radius (r>0.6) internal transport barrier (ITB), often observed in all channels (ne, Te, Ti, rotation), and responsible for both excellent energy confinement quality and excellent stability properties. Experiments on DIII-D have shown that, with a largeradius ITB, very high βN and βP values (both≥4) can be reached by taking advantage of the stabilizing effect of a nearby conducting wall. Synergistically, higher plasma pressure provides turbulence suppression by Shafranov shift, leading to ITB sustainment independent of the plasma rotation. Experiments on EAST have been used to assess the long pulse potential of the high-βP regime. Using RF-only heating and current drive, EAST achieved minute-long fully noninductive steady state H-mode operation with strike points on an ITER-like tungsten divertor. Improved confinement (relative to standard H-mode) and steady state ITB features are observed with a monotonic q-profile with qmin~1.5. Separately, experiments have shown that increasing the density in plasmas driven by lower hybrid wave broadens the q-profile, a technique that could enable a large radius ITB. These experimental results have been used to validate MHD, current drive, and turbulent transport models, and to project the high-βP regime to a burning plasma. These projections suggest the Shafranov shift alone will not suffice to provide improved confinement (over standard H-mode) without rotation and rotation shear. However, increasing the negative magnetic shear (higher q on axis) provides a similar turbulence suppression mechanism to Shafranov shift, and can help devices such as ITER and CFETR achieve their steady-state fusion goals.
- Research Organization:
- Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA)
- Grant/Contract Number:
- AC52-07NA27344
- OSTI ID:
- 1502029
- Alternate ID(s):
- OSTI ID: 23001440
- Report Number(s):
- LLNL-JRNL--758197; 943646
- Journal Information:
- Plasma Physics and Controlled Fusion, Journal Name: Plasma Physics and Controlled Fusion Journal Issue: 1 Vol. 60; ISSN 0741-3335
- Publisher:
- IOP ScienceCopyright Statement
- Country of Publication:
- United States
- Language:
- English
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